ML17258A980: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:QUALITY'ASSURANCEMANUALGINNASTATIONREV.PAGE422AEFFECTIVEDATEE"ROCHESTERGAS&ELECTRIC'CORPORATIONay,81SIGNATUREDATETITLEAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalPREPAREDBYQUALITYASSURANCEREVIEWAPPROVEDBY:V/~i/S(ProramTableofContentsIntroduction:Program:DiscussionISI1.0ScopeandResponsibilityISI,2.0ISI3.0.InspectionIntervalsExtentandFrequencyISI4.0ExaminationMethodsISI5.0EvaluationofExaminationResultsISI6.0RepairRequirementsIISI7.0SystemPressureTestingISI8.0ISI9.0RecordsandReportsExemptions
{{#Wiki_filter:QUALITY'ASSURANCE MANUALGINNASTATIONREV.PAGE422AEFFECTIVE DATEE"ROCHESTER GAS&ELECTRIC'CORPORATION ay,81SIGNATURE DATETITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPREPAREDBYQUALITYASSURANCE REVIEWAPPROVEDBY:V/~i/S(ProramTableofContentsIntroduction:
Program:Discussion ISI1.0ScopeandResponsibility ISI,2.0ISI3.0.Inspection Intervals ExtentandFrequency ISI4.0Examination MethodsISI5.0Evaluation ofExamination ResultsISI6.0RepairRequirements IISI7.0SystemPressureTestingISI8.0ISI9.0RecordsandReportsExemptions


==References:==
==References:==
Tables:ISI1.1QualityGroupAComponents,PartsandMethodofExaminationISI1.2QualityGroupBComponents,PartsandMethodofExaminationAttachmentA-Quality,GroupsA,B,and.CExemptions ICIrpI QUALITYASSURANCEMANUALGINNASTATIONTITLE)APPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/81222OF4252CINTRODUCTIONAppendix'Bof.thisQuali~tyAssuranceManualdescribesGinna'sInserviceInspection'rogramforthe120monthinspectionintervalcommencingJanuary1,1980andendingDecember31,1989.Includedinthisprogramarethefollowingportionsof-systemsand/orcomponents:QualityGroupAComponentsQualityGroupBComponentsQualityGroupCComponentsHighEnergyPipingOutsideofContainmentSteamGeneratorTubingReactorCoolantPumpFlywheelsFollowingtheguidanceofReference1,SectionXIoftheCode,Ginna'sInserviceInspectionProgramadherestothere-quirementsofSection50.55aoftheCodeofFederalRegulations,Reference2.Thisprogram,however,excludesthecontrolsoftheAuthorizedNuclearInspector,EnforcementAuthority,Re-portingSystems,'andN-StampISymbol.TheInserviceInspection'rogramforQualityGroupsA,BandCcomponents,asdefinedinRegulatoryGuide1.26,Refer-ence3,iscontrolledbyGinna'sQualityAssuranceProgramforStationOperation.Thissameprogramwhichisalsoincompliancewiththe,referencedSectionXI,providesthemostacceptableguidelinesandlatesttechniquescurrentlybeingutilizedintheperformanceofaninserviceinspection.RepairstoQualityGroupsA,BandCcomponentsshallbeperformedinaccordancewiththeOwner'sDesignSpecificationandConstructionCodeofthecomponentorsystem.LatereditionsoftheConstructio'nCodeorASMESectionIII,eitherinitsentiretyorportionsthereof,canalsobeused.Ifrepairweldingcannotbeperformedinaccordancewiththeserequirements,thenArticle4000ofReference11willbeused.AsindicatedinRochesterGasandElectric'sreport/Reference4,andAugmentedInserviceInspectionProgramforhighenergypipingoutsideofcontainmenthasbeenes-tablished.Theinspectionprogramprovidesforvolumetricexaminationonallcircumferentialbuttweldssituatedatdesignbreaklocationsoratdiscontinuitylocationswhereprobablefailurecouldoccur.Surveillanceofthesewelds 0IP QUALITYASSURANCEMANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/813F22candetectmaterialchangesinadvanceofapotentialfailure,therebyassuringthatthedesignbasisorconsequentialmainsteamorfeedwaterbreakwillnotoccur.TheInserviceInspectionProgramforsteamgeneratortubeswasdevelopedtomeettheguidanceofReference5.Atregularintervals,tubeswithineachlegofthesteamgeneratorareexaminedandevaluatedforacceptabletubewallthickness.TheInserviceInspectionProgramforreactorcoolantpumpflywheelswasdevelopedtomeettheguidanceofReference12.Attheintervalssuggested,thereactorcoolantpumpflywheelwillbeexaminedbyeitherthevolumetricorsurfaceexami-nationmethod,andevaluatedtothespecifiedacceptancecriteria.IdentificationisgiveninSection9.0ofGinna'sInserviceInspectionProgramforthoseareaswhichdeviatefromtherequirementsofReference1.Whereapplicable,currentlyapprovededitionandaddendasofSectionXIwillbeutilizedforclarificationandguidance.ItistheintentofRochesterGasandElectricCorporation,tocontinuallyapplyappropriatechangesintheCodewhichimprovestheoverallqualityofGinna'stotalInserviceInspectionProgram.PROGRAMISI1.0ScoeandResonsibilitComponentsofQualityGroupsAandBarelistedinTablesISI-1.1and1.2,respectively.QualityGroupCcomponentsareidentifiedinAppendixAofGinna'sQualityAssuranceManual.ThespecificcomponentstobeexaminedforeachQualityGroupshallbedefinedintheExaminationPlansbytitleand/ornumber.1.2TheInserviceInspectionProgramforhighenergypipingoutsideofcontainmentconsistsofmainsteamandfeedwaterpipingweldsisdetailedintheExaminationPlanforHighEnergyPiping.
 
0gllAuII QUALITYASSURANCEMANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/814224252C1.3TheInserviceInspectionProgramforsteamgeneratortubes,whichisoutlinedinthispro-gram,wasdevelopedtotheguidanceprovidedinReference5,.isIdetailedinGinna'sstationprocedures.1.4TheInserviceInspectionProgramforreactorcoolantpumpflywheels,whichisoutlinedinthisprogram,wasdevelopedtotheguidancepro-videdinReference12,isdetailedinGinna'sstationprocedures.ISI2.0Insec'tionIntervals2.12.2Theinserviceinspection(ISI)intervalsforQualityGroupAcomponentsshallbetenyearintervalsofservicecommencingJanuary1,1970.ThisprogramdefinestheISIrequirementsforthesecondintervalforQualityGroupAcomponents.Thetenyearexaminationplanshalldescribethe'istributionofexaminationswithintheinspectionintervalinaccordancewithIWB-2400ofReference1~TheinserviceinspectionintervalsforQualityGroupBcomponentsshallbetenyearintervalsofservicecommencingonJanuary1,1970.ThisprogramdefinestheISIrequirementsforthesecondintervalforQualityGroupBcomponents.ThetenyearexaminationplanshalldescribethedistributionofexaminationswithintheinspectionintervalinaccordancewithIWC-2400ofReference1.2.3TheinserviceinspectionintervalsforQualityGroupCcomponentsshallbetenyearintervalsofservicecommencingonJanuary1,1970.ThisprogramdefinestheISIrequirementsforthesecondintervalQualityGroupCcomponents.ThetenyearexaminationplanshalldescribethedistributionofexaminationswithintheinspectionintervalinaccordancewithIWD-2400ofReference1.
Tables:ISI1.1QualityGroupAComponents, PartsandMethodofExamination ISI1.2QualityGroupBComponents, PartsandMethodofExamination Attachment A-Quality,GroupsA,B,and.CExemptions ICIrpI QUALITYASSURANCE MANUALGINNASTATIONTITLE)APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/81222OF4252CINTRODUCTION Appendix'Bof.thisQuali~tyAssurance Manualdescribes Ginna'sInservice Inspection'rogram forthe120monthinspection intervalcommencing January1,1980andendingDecember31,1989.Includedinthisprogramarethefollowing portionsof-systemsand/orcomponents:
rl QUALITYASSURANCEMANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGEOF225/01/812.4TheinserviceinspectionintervalsforthehighenergypipingoutsideofcontainmentshallbetenyearintervalsofservicecommencingMay1,1973.ThetenyearexaminationplanshalldescribethedistributionofexaminationswithintheinspectionintervalinaccordancewiththerequirementsofReference4.2.5Theinserviceinspectionintervalsfortheexami-nationofsteamgeneratortubesshallnotbemorethan24months.However,ifoveranominal2yearperiod(e.g.,twonormalfuelcycles)atleast2examinationsoftheseparatelegsresultinlessthan10%ofthe.tubeswithdetectablewallpenetration(T20%)andnosignificant(710%)furtherpenetrationoftubeswithpreviousindi-cations,theinspectionintervaloftheindividuallegsmaybeextendedtoonceevery40months.2.6AspermittedbyIWA-2400ofReference1,theinserviceinspectionintervalforQualityGroupsA,BandCandhighenergypipingoutsidecon-tainmentmaybeextendedasnecessary.2.7Theinserviceinspectionintervalsforthereactorcoolantpumpflywheelshallbeapproximately10yearintervalsofservice.commencingonJanuary1,1970.Forareasofhighstressconcentrationattheboreandkeyway,areducedintervalofapproxi-mately3years'shallbeapplied.ThetenyearexaminationplanshalldescribethedistributionofexaminationswithintheinspectionintervalinaccordancewiththerequirementsofReference12.ISI3.03.1ExtentandFreuencrQualityGroupAcomponents,aslistedinTableISI-1.1shallbeexaminedtotheextentandfrequencyasrequiredinTableIWB-2500ofRefer-ence1.
QualityGroupAComponents QualityGroupBComponents QualityGroupCComponents HighEnergyPipingOutsideofContainment SteamGenerator TubingReactorCoolantPumpFlywheels Following theguidanceofReference 1,SectionXIoftheCode,Ginna'sInservice Inspection Programadherestothere-quirements ofSection50.55aoftheCodeofFederalRegulations, Reference 2.Thisprogram,however,excludesthecontrolsoftheAuthorized NuclearInspector, Enforcement Authority, Re-portingSystems,'andN-StampISymbol.TheInservice Inspection'rogram forQualityGroupsA,BandCcomponents, asdefinedinRegulatory Guide1.26,Refer-ence3,iscontrolled byGinna'sQualityAssurance ProgramforStationOperation.
IJt QUALITYASSURANCEMANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalPAGE6OF22DATE5/01/813.2QualityGroupBcomponents,aslistedinTableISI-1.2,shallbeexaminedtotheextentandfrequencyasrequiredinTableIWC-2500ofReference1.3.3QualityGroupCcomponentsasdescribedinthetenyearexaminationplanshallbeexaminedtotheextentandfrequencyrequiredinIWD-2400andIWD-2600ofReference1.3.4Highenergypipingweldsoutsideofcontainmentshallbeexaminedtothefollowingextentandfrequency:3.4.1Duringeachperiodofthefirstinspectioninter-val,allweldsat.designbreaklocationsandone-thirdofallweldsatlocationswhere'weldfailurewouldresultinunacceptableconsequences,willbevolumetricallyexamined.3.4.2Duringeachperiodofsucceedingintervals,one-thirdofallweldsatdesignbreaklocationsandone-thirdofallweldsatlocationswhereaweldfailurewouldresultinunacceptableconsequences,shallbevolumetricallyexamined.3.5TheextentandselectionofsteamgeneratortubeexaminationsshallbeasdescribedinSectionsC.4andC.5ofReference5,withtheinterpretationthatexaminationinalegofallpreviouslydefectivetubes(Q20%detectablewall'enetration)anduptoamaximumoftwohundredpreviouslydefect-freetubes(420%detectablewallpene-tration)isdeemedsufficientinmeetingtherequirementsofReference5.3.5.1Intheeventaprimarytosecondaryleakexceedstechnicalspecificationlimit,alimitednumberoftubesshallbeexaminedatthenextrefuelingoutage.3.5.2Intheeventofaseismicoccurancegreaterthanthatforwhichtheplantisdesignedtocontinueoperation,Reference6,aspecialexaminationofalimitednumberoftubesshallbeconducted.
Thissameprogramwhichisalsoincompliance withthe,referenced SectionXI,providesthemostacceptable guidelines andlatesttechniques currently beingutilizedintheperformance ofaninservice inspection.
foIi'HtIP4I QUALITYASSURANCEMANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/81722OF3.5.3Intheeventofamajorsteamlineorfeedwaterlinebreak,oraloss-of-coolantaccident(LOCA)whichimposesasignificantpressuretransientonthesteamgeneratorsandrequiresactuationoftheengineeredsafe-guards,aspecialexami-nationofalimitednumberoftubesshallbeconducted.3.6Thereactorcoolantpumpflywheel,listedinTableISI-1.1,shallbeexaminedtotheextentandfrequencyasrequiredinReference12.ISI4.0ExaminationMethods4.1QualityGroupsAandBcomponentsshallbeexaminedbytherequiredvisual,surfaceorvolumetricmethods.Theseexaminationsshallincludeoneoracombinationofthefollowing:visual,liquidpenetrant,magneticparticle,ultrasonic,eddy-currentorradiographicexami-nation.Thesemethods,shallasaminimum,beinaccordancewj.ththerulesofIWA-2000ofReference1.4.1.14.1.1.1Ultrasonicexaminationsshallbeperformedinaccordancewiththefollowing:Forferriticvesselswithwallthicknessof2-1/2inchesorgreater',anultrasonicexaminationshallbeconductedinaccordancewiththerulesofAppendixIofReference1.4.1.1.24.1.1.3Forferriticpipingsystems,anultrasonicexami-nationshallbeconductedinaccordancewiththerulesofAppendixIIIofReference7.Forcomponentsotherthanthoselistedin4.1.1.1and4.1.1.2,anultrasonicexaminationshallbeconductedinaccordancewiththerulesofArticle5ofReference8.4.1.1.4Allindicationswhichproducearesponsegreaterthan,50%ofthereferencelevelshallberecorded.
RepairstoQualityGroupsA,BandCcomponents shallbeperformed inaccordance withtheOwner'sDesignSpecification andConstruction Codeofthecomponent orsystem.LatereditionsoftheConstructio'n CodeorASMESectionIII,eitherinitsentiretyorportionsthereof,canalsobeused.Ifrepairweldingcannotbeperformed inaccordance withtheserequirements, thenArticle4000ofReference 11willbeused.Asindicated inRochester GasandElectric's report/Reference 4,andAugmented Inservice Inspection Programforhighenergypipingoutsideofcontainment hasbeenes-tablished.
0f~'l QUALITYASSURANCEMANUALGINNASTATIONTITLEtAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/8182242~52C4.1.1.5Allindicationswhichproducearesponse~100%ofthereferencelevelshallbeinvestigatedtotheextentthat,theoperatorcanevaluatetheshape,identity',andlocationofallsuchre-flectorsintermsoftheacceptance/rejectionstandardsofIWA-3100(b)ofReference1.Thelengthofreflectorsshallbemeasuredbetweenpointswhichgiveamplitudesequalto100%ofthereferencelevel.4.2QualityGroupCcomponentsshallbevisuallyexaminedforleakageduringasystempressuretest.4.3Highenergypipingweldsoutsideofcontainmentshallberadiographicallyexamined.4.4Steamgeneratortubesshallbeexaminedbyavolumetricmethod(e.g.eddycurrent)oral-ternativemethodwhichisacceptable.4.5,ReactorcoolantIpumpflywheelsshallbeexaminedbytherequired;surfaceandvolumetricmethods,inaccordancewiththerequirementsofIWA-2200ofReference1.ISI5.0EvaluationofExaminationResults5.1TheevaluationofnondestructiveexaminationresultsshallbeinaccordancewithArticleIWB-3000ofReference1.Allreportableindicationsshallbesubjecttocomparisonwithpreviousdatatoaidinitscharacterizationandindeter-miningitsorigin.5.25.2.1QualityGroupBComponentsTheevaluationofnondestructiveexaminationre-sultsshallbeinaccordancewithArticleIWC-3000ofReference1.Allreportableindicationsshallbesubjecttocomparisonwithpreviousdatatoaidinitscharacterizationandindeterminingitsorigin.5.3QualityGroupCComponents c~Aj"IJ QUALITYASSURANCEMANUALGINNA"STATIONTITLE:APPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE5/01/8122OF4252C5.3.1TheevaluationofthevisualexaminationresultsshallbeinaccordancewithArticleIWA-5000ofReference1.5.4HighEnergyPiping5.4.1TheevaluationofnondestructiveexaminationresultsshallbeinaccordancewithReference9.5.5Indicationsthatwererecordedinpreviouspre-serviceorinserviceinspectionsandwhichwerenotcharacterizedaspropagatingflawsareacceptableforcontinuedservice.5.6TheevaluationofanycorrodedareashallbeperformedinaccordancewithArticleIWA-5000ofReference11.5.7SteamGeneratorTubesandTubeSleeveCombinations5.7.1Theevaluationofnondestructiveexaminationresultsshallbeasfollows:5.7.1.1Plantoperationmayresumewhenalltubesandsleevesarewithinacceptablewallthicknesscriteriaandtheconditionsof(a)or(b)aremet:(a)Whenlessthan10percentofpreviouslydefect-freetubesorsleevesexamined,(i.e.C20%ofwallpenetration)havedevelopeddetectablewallpenetrationsofgreaterthan20%,or(b)WhenpreviouslydegradedtubesorsleevesexhibitfurtherwallpenetrationofC10%.NOTE:AnacceptabletubewallthicknessisonewhichcansustainaLOCAincombinationwithaseismicoccurrence,forwhichtheplantisdesignedtocontinueoperation,withoutalossoffunctiontoClass1systems,Reference8.Sleevesmaybeusedtoprovideanacceptabletube.
Theinspection programprovidesforvolumetric examination onallcircumferential buttweldssituatedatdesignbreaklocations oratdiscontinuity locations whereprobablefailurecouldoccur.Surveillance ofthesewelds 0IP QUALITYASSURANCE MANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/813F22candetectmaterialchangesinadvanceofapotential failure,therebyassuringthatthedesignbasisorconsequential mainsteamorfeedwater breakwillnotoccur.TheInservice Inspection Programforsteamgenerator tubeswasdeveloped tomeettheguidanceofReference 5.Atregularintervals, tubeswithineachlegofthesteamgenerator areexaminedandevaluated foracceptable tubewallthickness.
J(flN0/I.J1V QUALITYASSURANCEMANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATE5/01/81PAGE10OF4C225.7.1.25.7.1.35.7.1.4Ifnomorethan3tubesorsleeveshaveunacceptablewallthicknessandthecriteriaof5.7.1.1areotherwisemet,plantoperationmayresumeaftercorrectivemeasureshavebeentaken.Whentheabovecriteriaarenotmet,thesituationshallbeimmediatelyreportedtotheNuclearRegulatoryCommission.Plantoperationmayresumeaftercorrectivemeasuresaretaken.All'bnormaldegradationofsteamgeneratortubesshallbereportedwithaLicenseeEvent,Report(LER)inaccordancewithTechnicalSpecificationrequire-,ments.SteamgeneratortubesthathavedefectindicationsP40%throughwall,asindicatedbyeddycurrent,shallberepairedbypluggingorbysleeving."Steamgeneratorsleevesthathavedefectindi-cations+30%throughwall,asindicatedbyeddycurrent,shallberepairedbyplugging.ISI6.0ReairReuirements6.1RepairofQualityGroupsA,BandCcomponentsshallbeperformedinaccordancewiththeappli-cableSubsectionsofReference11.6.26.2.1Examinationsassociatedwithrepairsormodifi-cationsshallmeettheapplicabledesignandinspectionCoderequirementsasdescribedinthefollowingparagraphs:WheneverQualityGroupsA,BorCSystemmodifi-cationsorrepairshavebeenmadewhichinvolvenewstrengthweldsoncomponentsgreaterthan2inchesdiameter,thenewweldsshallreceivebothsurfaceand100percentvolumetricnondestructiveexaminations.6.2.2WheneversystemmodificationsorrepairshavebeenmadewhichinvolvenewstrengthweldsonQualityGroupsA,BorCcomponentsof2inchesorless,asurfaceexaminationshallbeperformed.
TheInservice Inspection Programforreactorcoolantpumpflywheels wasdeveloped tomeettheguidanceofReference 12.Attheintervals suggested, thereactorcoolantpumpflywheelwillbeexaminedbyeitherthevolumetric orsurfaceexami-nationmethod,andevaluated tothespecified acceptance criteria.
QUALITYASSURANCEMANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATE5/01/81PAGE11OF22426RC6.3SurfacedefectsinQualityGroupsA,BorCbolts,studs,nutsandligamentsmayberemovedbymechanicalmeansprovidedtheremovalofthatdefectdoesnotalterthebasicconfigurationoftheitem.Bolts,studsandnutsthathavede-fectsthatcannotberemovedbymechanicalmeansshallbereplaced.6.4RepairofhighenergypipingweldsoutsideofcontainmentshallbeperformedinaccordancewiththeapplicableCodespecifiedinReference11.6.5RepairofSteamGeneratorTubes6.5.1Repairofsteamgeneratortubesthathaveunaccept-,abledefectsshallbeperformedbyusingatubepluggingtechniqueorbysleeving.Ifsleevingistobeperformedtherequirementsof6.5.3mustbeimplemented.6.5.2Preventativesleevingoftubesaspartofapre-ventativemaintenance.programmayalsobeaccom-plishedprovidedtherequirementsof6.5.3aremet.6.5.3Duringeachsteamgeneratorinspectionamaximumof25sleevesmaybeinstalledineachsteamgeneratorforrepairorpreventativemaintenance.AnyadditionalsleeveinstallationshallrequiretheapprovaloftheNuclearRegulatoryCommisssion,NuclearReactorRegulationBranch.6.6,Repairofsteamgeneratorsleevesthathaveunacceptabledefectsshallbeperformedbyusingatubepluggingtechnique.6.7ISI7-0RepairofreactorcoolantpumpflywheelthathaveunacceptabledefectsshallbeperformedinaccordancewithReference12.SstemPressureTestin7.1GeneralRequirements7.1.1SystempressuretestshallbeconductedinaccordancewithArticleIWA-5000ofReference11.
Identification isgiveninSection9.0ofGinna'sInservice Inspection Programforthoseareaswhichdeviatefromtherequirements ofReference 1.Whereapplicable, currently approvededitionandaddendasofSectionXIwillbeutilizedforclarification andguidance.
QUALITYASSURANCEMANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATE5/01/81PAGE12OF42~52C227.1.2RepairsofcorrodedareasshallbeperformedinaccordancewithSection6.0ofthisprogram.7.2QualityGroupAComponents7.2.1Wheneverthereactorcoolantsystemisclosedafterithasbeenopened,thesystemshallbeleaktestedtotherequirementsofArticleIWB-5000ofReference11.TemperatureandpressurerequirementsofFigure3.1-1,Section3.1ofGinna's"TechnicalSpecifications"shallnotbeexceeded.7.2.2Atorneartheendofeachinspectioninterval,ahydrostaticpressuretestshallbeperformedonthereactorcoolantsystemcomponents.Thistestshallbeconductedinaccordancewiththerequire-mentsofArticleIWB-5000ofReference11.Testpressuresandtemperaturesshallbemaintainedforatleastfourhourspriortoperformingthevisualexamination.Section3.1ofGinna's"TechnicalSpecification"shallnotbeexceeded.7.3QualityGroupBComponents7.3.1Atorneartheendofeachinspect'ioninterval,ahydrostaticpressuretestshallbeperformedonQualityGroupBSystemsandComponents.ThistestshallbeconductedinaccordancewiththerequirementsofArticleIWC-5000ofReference11.WhenQualityGroupAsystemsandcomponentsarealsobeingpressurized,thepressureandtemper-atureshallcomplywiththerequirementsofParagraph7.2.2ofthisAppendix.Thistesttemperatureandpressureshallbemaintainedforatleast10minutespriortotheperformanceofthevisualexamination.7.4QualityGroupCComponents7.4.1QualityGroupCcomponentsshallhavesystempressuretestinaccordancewithArticleIWD-5000ofReference11.
ItistheintentofRochester GasandElectricCorporation, tocontinually applyappropriate changesintheCodewhichimprovestheoverallqualityofGinna'stotalInservice Inspection Program.PROGRAMISI1.0ScoeandResonsibilit Components ofQualityGroupsAandBarelistedinTablesISI-1.1and1.2,respectively.
5<~,t1F, QUALITYASSURANCE'ANUALGINNASTATIONTITLEeAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalPAGE5/01/81OF4252C22ISI8.0RecordsandReorts8.1Recordsandreportsdevelopedfromthoseexami-nationsperformedinaccordancewiththisAppendixshallbemaintainedinaccordancewithArticleIWA-6000ofReference11.ISI9-0Exemtions9.1QualityGroupsA,BandCcomponentsexemptionsareidentifiedinAttachmentAtothisAppendix.However,ParagraphsIWB-1220andIWC-1220ofReference1exemptcertaincomponentsfromexami-nations,wherecertainconditionsaremet.TheseexemptionswillbeappliedtothecomponentslistedonTablesISI-1.1and1.2withtheresultthat.onlythosenon-exemptcomponentsarelistedherein.REFERENCES1.AmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVesselCode(B&PVC)SectionXI"RulesforInserviceInspectionofNuclearPowerPlantComponents",1974EditionthroughSummer1975Addenda.2.CodeofFederalRegulations,Title10,Part50,datedJanuary1,1978.3.NuclearRegulatoryCommission,RegulatoryGuide1.26,Revision1,datedFebruary1976"Quality-GroupClassifi-cationsandStandardsforWater,Steam,andRadioactiveWaste-ContainingComponentsofNuclearPowerPlants".4.RochesterGasandElectricCorporationReport"EffectsofPostulatedPipeBreaksOutsidetheContainmentBuilding",datedOctober29,1973.5.NuclearRegulatoryCommission,RegulatoryGuide1.83,Revision1,datedJuly1975,"InserviceInspectionofPressurizedWaterReactorSteamGeneratorTubes".6.Ginna'sFinalSafetyAnalysisReport,Section2.9.3.7.ASME,BGPVC,SectionXI,1974EditionthroughSummer1976Addenda.  
QualityGroupCcomponents areidentified inAppendixAofGinna'sQualityAssurance Manual.Thespecificcomponents tobeexaminedforeachQualityGroupshallbedefinedintheExamination Plansbytitleand/ornumber.1.2TheInservice Inspection Programforhighenergypipingoutsideofcontainment consistsofmainsteamandfeedwater pipingweldsisdetailedintheExamination PlanforHighEnergyPiping.
0gllAuII QUALITYASSURANCEMANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/814224252C1.3TheInservice Inspection Programforsteamgenerator tubes,whichisoutlinedinthispro-gram,wasdeveloped totheguidanceprovidedinReference 5,.isIdetailedinGinna'sstationprocedures.
1.4TheInservice Inspection Programforreactorcoolantpumpflywheels, whichisoutlinedinthisprogram,wasdeveloped totheguidancepro-videdinReference 12,isdetailedinGinna'sstationprocedures.
ISI2.0Insec'tionIntervals 2.12.2Theinservice inspection (ISI)intervals forQualityGroupAcomponents shallbetenyearintervals ofservicecommencing January1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalforQualityGroupAcomponents.
Thetenyearexamination planshalldescribethe'istribution ofexaminations withintheinspection intervalinaccordance withIWB-2400ofReference 1~Theinservice inspection intervals forQualityGroupBcomponents shallbetenyearintervals ofservicecommencing onJanuary1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalforQualityGroupBcomponents.
Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withIWC-2400ofReference 1.2.3Theinservice inspection intervals forQualityGroupCcomponents shallbetenyearintervals ofservicecommencing onJanuary1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalQualityGroupCcomponents.
Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withIWD-2400ofReference
: 1.
rl QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGEOF225/01/812.4Theinservice inspection intervals forthehighenergypipingoutsideofcontainment shallbetenyearintervals ofservicecommencing May1,1973.Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withtherequirements ofReference 4.2.5Theinservice inspection intervals fortheexami-nationofsteamgenerator tubesshallnotbemorethan24months.However,ifoveranominal2yearperiod(e.g.,twonormalfuelcycles)atleast2examinations oftheseparatelegsresultinlessthan10%ofthe.tubeswithdetectable wallpenetration (T20%)andnosignificant (710%)furtherpenetration oftubeswithpreviousindi-cations,theinspection intervaloftheindividual legsmaybeextendedtoonceevery40months.2.6Aspermitted byIWA-2400ofReference 1,theinservice inspection intervalforQualityGroupsA,BandCandhighenergypipingoutsidecon-tainmentmaybeextendedasnecessary.
2.7Theinservice inspection intervals forthereactorcoolantpumpflywheelshallbeapproximately 10yearintervals ofservice.commencing onJanuary1,1970.Forareasofhighstressconcentration attheboreandkeyway,areducedintervalofapproxi-mately3years'shall beapplied.Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withtherequirements ofReference 12.ISI3.03.1ExtentandFreuencrQualityGroupAcomponents, aslistedinTableISI-1.1shallbeexaminedtotheextentandfrequency asrequiredinTableIWB-2500ofRefer-ence1.
IJt QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPAGE6OF22DATE5/01/813.2QualityGroupBcomponents, aslistedinTableISI-1.2,shallbeexaminedtotheextentandfrequency asrequiredinTableIWC-2500ofReference 1.3.3QualityGroupCcomponents asdescribed inthetenyearexamination planshallbeexaminedtotheextentandfrequency requiredinIWD-2400andIWD-2600ofReference 1.3.4Highenergypipingweldsoutsideofcontainment shallbeexaminedtothefollowing extentandfrequency:
3.4.1Duringeachperiodofthefirstinspection inter-val,allweldsat.designbreaklocations andone-thirdofallweldsatlocations where'weldfailurewouldresultinunacceptable consequences, willbevolumetrically examined.
3.4.2Duringeachperiodofsucceeding intervals, one-thirdofallweldsatdesignbreaklocations andone-third ofallweldsatlocations whereaweldfailurewouldresultinunacceptable consequences, shallbevolumetrically examined.
3.5Theextentandselection ofsteamgenerator tubeexaminations shallbeasdescribed inSectionsC.4andC.5ofReference 5,withtheinterpretation thatexamination inalegofallpreviously defective tubes(Q20%detectable wall'enetration) anduptoamaximumoftwohundredpreviously defect-free tubes(420%detectable wallpene-tration)isdeemedsufficient inmeetingtherequirements ofReference 5.3.5.1Intheeventaprimarytosecondary leakexceedstechnical specification limit,alimitednumberoftubesshallbeexaminedatthenextrefueling outage.3.5.2Intheeventofaseismicoccurance greaterthanthatforwhichtheplantisdesignedtocontinueoperation, Reference 6,aspecialexamination ofalimitednumberoftubesshallbeconducted.
foIi'HtIP4I QUALITYASSURANCE MANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/81722OF3.5.3Intheeventofamajorsteamlineorfeedwater linebreak,oraloss-of-coolant accident(LOCA)whichimposesasignificant pressuretransient onthesteamgenerators andrequiresactuation oftheengineered safe-guards, aspecialexami-nationofalimitednumberoftubesshallbeconducted.
3.6Thereactorcoolantpumpflywheel, listedinTableISI-1.1,shallbeexaminedtotheextentandfrequency asrequiredinReference 12.ISI4.0Examination Methods4.1QualityGroupsAandBcomponents shallbeexaminedbytherequiredvisual,surfaceorvolumetric methods.Theseexaminations shallincludeoneoracombination ofthefollowing:
visual,liquidpenetrant, magneticparticle, ultrasonic, eddy-current orradiographic exami-nation.Thesemethods,shallasaminimum,beinaccordance wj.ththerulesofIWA-2000ofReference 1.4.1.14.1.1.1Ultrasonic examinations shallbeperformed inaccordance withthefollowing:
Forferriticvesselswithwallthickness of2-1/2inchesorgreater',
anultrasonic examination shallbeconducted inaccordance withtherulesofAppendixIofReference 1.4.1.1.24.1.1.3Forferriticpipingsystems,anultrasonic exami-nationshallbeconducted inaccordance withtherulesofAppendixIIIofReference 7.Forcomponents otherthanthoselistedin4.1.1.1and4.1.1.2,anultrasonic examination shallbeconducted inaccordance withtherulesofArticle5ofReference 8.4.1.1.4Allindications whichproducearesponsegreaterthan,50%ofthereference levelshallberecorded.
0f~'l QUALITYASSURANCE MANUALGINNASTATIONTITLEtAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/8182242~52C4.1.1.5Allindications whichproducearesponse~100%ofthereference levelshallbeinvestigated totheextentthat,theoperatorcanevaluatetheshape,identity',
andlocationofallsuchre-flectorsintermsoftheacceptance/rejection standards ofIWA-3100(b)ofReference 1.Thelengthofreflectors shallbemeasuredbetweenpointswhichgiveamplitudes equalto100%ofthereference level.4.2QualityGroupCcomponents shallbevisuallyexaminedforleakageduringasystempressuretest.4.3Highenergypipingweldsoutsideofcontainment shallberadiographically examined.
4.4Steamgenerator tubesshallbeexaminedbyavolumetric method(e.g.eddycurrent)oral-ternative methodwhichisacceptable.
4.5,ReactorcoolantIpumpflywheelsshallbeexaminedbytherequired;surface andvolumetric methods,inaccordance withtherequirements ofIWA-2200ofReference 1.ISI5.0Evaluation ofExamination Results5.1Theevaluation ofnondestructive examination resultsshallbeinaccordance withArticleIWB-3000ofReference 1.Allreportable indications shallbesubjecttocomparison withpreviousdatatoaidinitscharacterization andindeter-miningitsorigin.5.25.2.1QualityGroupBComponents Theevaluation ofnondestructive examination re-sultsshallbeinaccordance withArticleIWC-3000ofReference 1.Allreportable indications shallbesubjecttocomparison withpreviousdatatoaidinitscharacterization andindetermining itsorigin.5.3QualityGroupCComponents c~Aj"IJ QUALITYASSURANCE MANUALGINNA"STATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/8122OF4252C5.3.1Theevaluation ofthevisualexamination resultsshallbeinaccordance withArticleIWA-5000ofReference 1.5.4HighEnergyPiping5.4.1Theevaluation ofnondestructive examination resultsshallbeinaccordance withReference 9.5.5Indications thatwererecordedinpreviouspre-serviceorinservice inspections andwhichwerenotcharacterized aspropagating flawsareacceptable forcontinued service.5.6Theevaluation ofanycorrodedareashallbeperformed inaccordance withArticleIWA-5000ofReference 11.5.7SteamGenerator TubesandTubeSleeveCombinations 5.7.1Theevaluation ofnondestructive examination resultsshallbeasfollows:5.7.1.1Plantoperation mayresumewhenalltubesandsleevesarewithinacceptable wallthickness criteriaandtheconditions of(a)or(b)aremet:(a)Whenlessthan10percentofpreviously defect-free tubesorsleevesexamined, (i.e.C20%ofwallpenetration) havedeveloped detectable wallpenetrations ofgreaterthan20%,or(b)Whenpreviously degradedtubesorsleevesexhibitfurtherwallpenetration ofC10%.NOTE:Anacceptable tubewallthickness isonewhichcansustainaLOCAincombination withaseismicoccurrence, forwhichtheplantisdesignedtocontinueoperation, withoutalossoffunctiontoClass1systems,Reference 8.Sleevesmaybeusedtoprovideanacceptable tube.
J(flN0/I.J1V QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE10OF4C225.7.1.25.7.1.35.7.1.4Ifnomorethan3tubesorsleeveshaveunacceptable wallthickness andthecriteriaof5.7.1.1areotherwise met,plantoperation mayresumeaftercorrective measureshavebeentaken.Whentheabovecriteriaarenotmet,thesituation shallbeimmediately reportedtotheNuclearRegulatory Commission.
Plantoperation mayresumeaftercorrective measuresaretaken.All'bnormal degradation ofsteamgenerator tubesshallbereportedwithaLicenseeEvent,Report(LER)inaccordance withTechnical Specification require-,ments.Steamgenerator tubesthathavedefectindications P40%throughwall,asindicated byeddycurrent,shallberepairedbypluggingorbysleeving."
Steamgenerator sleevesthathavedefectindi-cations+30%throughwall,asindicated byeddycurrent,shallberepairedbyplugging.
ISI6.0ReairReuirements 6.1RepairofQualityGroupsA,BandCcomponents shallbeperformed inaccordance withtheappli-cableSubsections ofReference 11.6.26.2.1Examinations associated withrepairsormodifi-cationsshallmeettheapplicable designandinspection Coderequirements asdescribed inthefollowing paragraphs:
WheneverQualityGroupsA,BorCSystemmodifi-cationsorrepairshavebeenmadewhichinvolvenewstrengthweldsoncomponents greaterthan2inchesdiameter, thenewweldsshallreceivebothsurfaceand100percentvolumetric nondestructive examinations.
6.2.2Wheneversystemmodifications orrepairshavebeenmadewhichinvolvenewstrengthweldsonQualityGroupsA,BorCcomponents of2inchesorless,asurfaceexamination shallbeperformed.
QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE11OF22426RC6.3SurfacedefectsinQualityGroupsA,BorCbolts,studs,nutsandligaments mayberemovedbymechanical meansprovidedtheremovalofthatdefectdoesnotalterthebasicconfiguration oftheitem.Bolts,studsandnutsthathavede-fectsthatcannotberemovedbymechanical meansshallbereplaced.
6.4Repairofhighenergypipingweldsoutsideofcontainment shallbeperformed inaccordance withtheapplicable Codespecified inReference 11.6.5RepairofSteamGenerator Tubes6.5.1Repairofsteamgenerator tubesthathaveunaccept-,
abledefectsshallbeperformed byusingatubepluggingtechnique orbysleeving.
Ifsleevingistobeperformed therequirements of6.5.3mustbeimplemented.
6.5.2Preventative sleevingoftubesaspartofapre-ventative maintenance
.programmayalsobeaccom-plishedprovidedtherequirements of6.5.3aremet.6.5.3Duringeachsteamgenerator inspection amaximumof25sleevesmaybeinstalled ineachsteamgenerator forrepairorpreventative maintenance.
Anyadditional sleeveinstallation shallrequiretheapprovaloftheNuclearRegulatory Commisssion, NuclearReactorRegulation Branch.6.6,Repairofsteamgenerator sleevesthathaveunacceptable defectsshallbeperformed byusingatubepluggingtechnique.
6.7ISI7-0Repairofreactorcoolantpumpflywheelthathaveunacceptable defectsshallbeperformed inaccordance withReference 12.SstemPressureTestin7.1GeneralRequirements 7.1.1Systempressuretestshallbeconducted inaccordance withArticleIWA-5000ofReference
: 11.
QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE12OF42~52C227.1.2Repairsofcorrodedareasshallbeperformed inaccordance withSection6.0ofthisprogram.7.2QualityGroupAComponents 7.2.1Wheneverthereactorcoolantsystemisclosedafterithasbeenopened,thesystemshallbeleaktestedtotherequirements ofArticleIWB-5000ofReference 11.Temperature andpressurerequirements ofFigure3.1-1,Section3.1ofGinna's"Technical Specifications" shallnotbeexceeded.
7.2.2Atorneartheendofeachinspection
: interval, ahydrostatic pressuretestshallbeperformed onthereactorcoolantsystemcomponents.
Thistestshallbeconducted inaccordance withtherequire-mentsofArticleIWB-5000ofReference 11.Testpressures andtemperatures shallbemaintained foratleastfourhourspriortoperforming thevisualexamination.
Section3.1ofGinna's"Technical Specification" shallnotbeexceeded.
7.3QualityGroupBComponents 7.3.1Atorneartheendofeachinspect'ion
: interval, ahydrostatic pressuretestshallbeperformed onQualityGroupBSystemsandComponents.
Thistestshallbeconducted inaccordance withtherequirements ofArticleIWC-5000ofReference 11.WhenQualityGroupAsystemsandcomponents arealsobeingpressurized, thepressureandtemper-atureshallcomplywiththerequirements ofParagraph 7.2.2ofthisAppendix.
Thistesttemperature andpressureshallbemaintained foratleast10minutespriortotheperformance ofthevisualexamination.
7.4QualityGroupCComponents 7.4.1QualityGroupCcomponents shallhavesystempressuretestinaccordance withArticleIWD-5000ofReference
: 11.
5<~,t1F, QUALITYASSURANCE
'ANUALGINNASTATIONTITLEeAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPAGE5/01/81OF4252C22ISI8.0RecordsandReorts8.1Recordsandreportsdeveloped fromthoseexami-nationsperformed inaccordance withthisAppendixshallbemaintained inaccordance withArticleIWA-6000ofReference 11.ISI9-0Exemtions9.1QualityGroupsA,BandCcomponents exemptions areidentified inAttachment AtothisAppendix.
However,Paragraphs IWB-1220andIWC-1220ofReference 1exemptcertaincomponents fromexami-nations,wherecertainconditions aremet.Theseexemptions willbeappliedtothecomponents listedonTablesISI-1.1and1.2withtheresultthat.onlythosenon-exempt components arelistedherein.REFERENCES 1.AmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCode(B&PVC)SectionXI"RulesforInservice Inspection ofNuclearPowerPlantComponents",
1974EditionthroughSummer1975Addenda.2.CodeofFederalRegulations, Title10,Part50,datedJanuary1,1978.3.NuclearRegulatory Commission, Regulatory Guide1.26,Revision1,datedFebruary1976"Quality-Group Classifi-cationsandStandards forWater,Steam,andRadioactive Waste-Containing Components ofNuclearPowerPlants".4.Rochester GasandElectricCorporation Report"EffectsofPostulated PipeBreaksOutsidetheContainment Building",
datedOctober29,1973.5.NuclearRegulatory Commission, Regulatory Guide1.83,Revision1,datedJuly1975,"Inservice Inspection ofPressurized WaterReactorSteamGenerator Tubes".6.Ginna'sFinalSafetyAnalysisReport,Section2.9.3.7.ASME,BGPVC,SectionXI,1974EditionthroughSummer1976Addenda.  
'Kl~JAl~eII(
'Kl~JAl~eII(
QUALITYASSURANCEMANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInserviceInspectionProgramForthe1980-1989IntervalDATEPAGE42~52C5/01/811422OF8.ASME,BGPVC,SectionV,1974EditionthroughSummer1975Addenda.9.USASB31.1.0-1967,"PowerPiping".10.ASME,BGPVC,SectionIII,1974EditionthroughSummer1975Addenda.11.ASME,B6PVCSectionXI,1977EditionthroughSummer1978Addenda.12.NuclearRegulatoryCommission,RegulatoryGuide1.14,Revision1,datedAugust.1975,"ReactorCoolantPumpFlywheelIntegrity".  
QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE42~52C5/01/811422OF8.ASME,BGPVC,SectionV,1974EditionthroughSummer1975Addenda.9.USASB31.1.0-1967,"PowerPiping".10.ASME,BGPVC,SectionIII,1974EditionthroughSummer1975Addenda.11.ASME,B6PVCSectionXI,1977EditionthroughSummer1978Addenda.12.NuclearRegulatory Commission, Regulatory Guide1.14,Revision1,datedAugust.1975,"ReactorCoolantPumpFlywheelIntegrity".  
~g~rik3),~P"'")fIp''g~pypi'lJ,J EXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1~1(Cont'd)COHPONFNTS,PARTS,ANDMETHODSOFEXAHINATIONCOMPONENTSANDPARTSTOBF.EXAHINFDMETHODQHRRZMx3WVM<<M<<RWQHPtON086.1008-G-186.110BW-188.30,8-H88.4083.98-P84.18-F87.30,BW-287.40HeatExchangersandSteamGeneratorsBoltsandstuds,whenremoved.Bolting.Integrally-weldedattachments.Exemptedcomponents.Bolts,studs,andnuts.PipingPressureBoundarySafe-endtopipingweldsandsafe-endinbranchpipingwelds.VolumetricandSurfaceVisualSurfaceVisual(IWA-5000)VisualVolumetricandSurfaceHQM86rt4er.e0OAr<<08c)V)5h3I'0we<<oU'ClQ<<tHm<<tQQOr%Hg0<<t'u8880Rjll986.150B-G-186.160B-G-186.170BW-I84.58-JBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Circumferentialandlongitudinalpipewelds.VolumetricVolumetricandSurfaceVisualVolumetricOOmVlCOI EXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)CONPONENTS,PARTS,ANDMETIIODSOFEXAMINATIONCOlfPONENTSANDPARTSTOBEFXAHINFDMFTHODQMRRZMIOWQMKUlCRWWHOQHId0PipingPressureBoundaryB4.6B-JB4.7B-JB4.8B10.10B-K-1B11.10B-K-2B4.11B-PB7~50BW-2Branchpipeconnectionweldssixinchdiameterandsmaller.SurfaceSocketwelds.Integrallyweldedattachments.Componentsupports.Exemptedcomponents.Bolts,studsand-nuts.SurfaceSurface.VisualVisual(IWA-5000)VisualPumpPressureBoundaryBranchpipeconnectionweldsexceedingsixinchVolumetricdiameter.HQIll8Illrt4III0IIIArvMIMEco55C)OlIllI'08MUClOCtMCortIllR'LoIQI.tdH5Qrt068QMIll9B6.180B-G-1B6.190B-G-1B6.200B-G-1B10.20B-K-1B11.20B-K-2Boltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrally-weldedattachments.Componentsupports.VolumetricVolumetricandSurfaceVisualSurfaceVisualVlCDCO5IN0
~g~rik3),~P"'")fIp''g~pypi'lJ,J EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1~1(Cont'd)COHPONFNTS, PARTS,ANDMETHODSOFEXAHINATION COMPONENTS ANDPARTSTOBF.EXAHINFDMETHODQHRRZMx3WVM<<M<<RWQHPtON086.1008-G-186.110BW-188.30,8-H88.4083.98-P84.18-F87.30,BW-287.40HeatExchangers andSteamGenerators Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.
Exemptedcomponents.
Bolts,studs,andnuts.PipingPressureBoundarySafe-endtopipingweldsandsafe-endinbranchpipingwelds.Volumetric andSurfaceVisualSurfaceVisual(IWA-5000)
VisualVolumetric andSurfaceHQM86rt4er.e0OAr<<08c)V)5h3I'0we<<oU'ClQ<<tHm<<tQQOr%Hg0<<t'u8880Rjll986.150B-G-186.160B-G-186.170BW-I84.58-JBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Circumferential andlongitudinal pipewelds.Volumetric Volumetric andSurfaceVisualVolumetric OOmVlCOI EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)CONPONENTS, PARTS,ANDMETIIODSOFEXAMINATION COlfPONENTS ANDPARTSTOBEFXAHINFDMFTHODQMRRZMIOWQMKUlCRWWHOQHId0PipingPressureBoundaryB4.6B-JB4.7B-JB4.8B10.10B-K-1B11.10B-K-2B4.11B-PB7~50BW-2Branchpipeconnection weldssixinchdiameterandsmaller.SurfaceSocketwelds.Integrally weldedattachments.
Component supports.
Exemptedcomponents.
Bolts,studsand-nuts.SurfaceSurface.VisualVisual(IWA-5000)
VisualPumpPressureBoundaryBranchpipeconnection weldsexceeding sixinchVolumetric diameter.
HQIll8Illrt4III0IIIArvMIMEco55C)OlIllI'08MUClOCtMCortIllR'LoIQI.tdH5Qrt068QMIll9B6.180B-G-1B6.190B-G-1B6.200B-G-1B10.20B-K-1B11.20B-K-2Boltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.
Component supports.
Volumetric Volumetric andSurfaceVisualSurfaceVisualVlCDCO5IN0
~~~
~~~
EXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS'ARTS'NDMFTllODSOFEXAMINATIONCOMPONENTSANDPARTSTOBEEXAMINEDMETIIODAHERMAWVCOClMCl.+~HO~HO<H0B5.6B-L-1B5.8B-PB7.60BW-2B6.210B-G-1B6.220B-G-1B6.230B-G-1B10.30B-K-1B11.30B-K-2B6.6B-M-1B6.8B-PB7.70BW-2PumpPressureBoundaryPumpcasingwelds.Exemptedcomponents.Bolts,studs,andnuts.ReactorCoolantPumpFlywheel.ValvePressureBoundaryBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrallyweldedattachments.Componentsupports.Valve-bodywelds.Fxemptedcomponents.Bolts,studs,andnuts.VolumetricVisualVisualVolumetricandSurfaceVolumetricVolumetricandSurfaceVisualVolumetricVisualVolumetricVisual(IWA-5000)VisualOH0Ul80rt4808AcDVlQltd)'d&SMUMAtt'Hco&Aft0t.CdHg0rtM880HPP8Im EXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS,PARTS,'NDMETIIODSOFEXAMINATIONCOMPONENTSANDPARTSTOBF.FXAHINEDMETIIODQMZchg3WWMCM~N.>RWNHANH0B6.60B-G-1B6.70B-G-1B3.1B-BB6.80B-G-1B8.20.B-HB2.10B-PB7.20B-G-2PressurizerCVBoltsandstuds,inplae.Boltsandstuds,whenremoved.Bolting.Integrally-weldedattachments.Fxemptedcomponents.Bolts,studs,andnuts.IIeatExchangersandSteamGeneratorsLongitudinalandcircumferentialwelds,includingTubesheet-to-headorshellweldsonthepri-maryside.VolumetricVolumetricandSurfaceVisualSurfaceVisual(IVA-5000)VisualVolumetricH0tn8eenOQr.vwM5eoddpC)0)5&6Mt]C)O0tH006'mr.rfOrtaMQ0rtM85809CmB3.2B3.3B-DB-FNozzle-to-headweldsandnozzleinsideradiusedsectionontheprimaryside.Nozzle-to-safe-endwelds.VolumetricVolumetricandSurfaceB6.90BW-1Boltsandstuds,inplace.Volumetric FXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONFNTS,PARTS,ANDMETIIODSOFEXAMINATIONCOMPONENTSANDPARTSToBF.FXAMINEDMETlIODAHRRchlOWWMclMc:QVHWWHO4H0B6.40BW-1B6.50B-G-1B7.10BW-2B8.10B-llB1.15B-N-1B1.17B-N-3B1.18B-OB1.19B-PReactorVesselLigamentsbetweenstudholes.ClosureWashers,bushings.Bolts,studsandnuts.Integrally-weldedattachments.VesselInterior.Core-supportstructures.Controlroddrivehousings.Exemptedcomponents.PressurizerVolumetricVisualVisualSurfaceVisual.VisualVolumetricVisual(IWA-5000)H0N8080,8ALOHQMPQotnQtuI'6ISMUtDQftH00ftQlMt'ft0I.tZIHg0rtMS8808B2.1B2.2B2.3B2.4B-BB-DB-FLongitudinalandcircumferentialwelds.Nozzle-to-vesselweldsandnozzle-to-vesselradiusedsection.lleaterpenetrations.Nozzle-to-safe-endwelds.VolumetricVolumetricVisual(IWA-5000)VolumetricandSurfaceOVlc)COOm EXAMINATIONCATEGORYITEMTABLENo.IWB-2500TABLEISI1.1QUALITYGROUPACOMPONENTS,PARTS,ANDMETHODSOFEXAHINATIONCOMPONENTSANDPARTSTOBEEXAMINEDHETHODAR3,'M&PNME2aAPMClXVONW0Bl.lB1.2B1.3B1.4B1.5B-AB-BB-DB-EReactorVesselLongitudinalandcircumferentialshallweldsincoreregion.Longitudinalandcircurmferentialweldsinshell{otherthanthoseofCategoryB-AandB-C)andmeridionalandcircumferentialbeamweldsinbottomheadandclosurehead(otherthanthoseofCategoryB-C).Vessel-to-flangeandhead-to-flangecircumferen-tialwelds.Primarynozzle-to-vesselweldsandnozzleinsidetiagwelds.Vesselpenetrations,includingcontrolroddriveandinstrumentationpenetrations.VolumetricVolumetricVolumetricVolumetricVisual(IWA-5000)H0M8ert4Kle0eQl'NmH5WmggMc)mQlh5>'dweMUwAAHco&m'EOt'N0Ito&50rtWe880gClm8Bl.6Nozzle-to-safe-endwelds.VolumetricandSurfaceB6.10B-G-1B6.20B-G-1B6.30B-G-1Closureheadnuts.Closurestuds,inplace.Closurestuds,whenremoved.SurfaceVolumetricVolumetricandSurface C1.1C-AC1.2C3.10C4.10C-DC3.20C3.30C-EC-EC2.1C2.2C2.3C-FeC-GC-F,CWC-F,CWC4.20C3.40C3.50C3.60C-DC-E-1C-E-2EXAMINATIONCATEGORYITFMTABLENo.IWC-2520TABLF.ISI1.2QUALITYGROUPBCOMPONENTS'ARTS'NDMFTllODSOFEXAHINATIONCOHPONENTSANDPARTSTOBEFXAHINEDPressureVesselsCircumferentialbuttvelds.Nozzle-to-vesslevelds.Integrally-weldedsupportattachments.Boltsandstuds.-Componentsupports.Supportsmechanicalandhydraulic.PipingCircumferentialbuttvelds.Longitudinalveld)ointsinfittings.Branchpipe-to-pipeveld)oints.Boltsandstuds.Integrallyveldedsupportattachments.Componentsupports.Supportsmechanicalandhyraulic.MF.TllODVolumetricVolumetricSurfaceVolumetricVisualVisualVolumetricVolumetricVolumetricVolumetricSurfaceVisualVisualOARP.M&WWvlc'sClWMcA<HW'H0lA88rt4808Q'EOH5co85'uotnmRI'0MS(OUu)OrtHmrtfuQ'LDt0I.lxlHg0rtMeN80mMm8VlCO EXAMINATIONCATEGORYITEMTABLENo.IWC-2520TABLEISI1.2(Cont'd)COMPONENTS,PARTSlANDMETIIODSOFEXAMINATIONCOMPONFNTSANDPARTSTOBEFXAMINEDMFTIIODQaplQRMIOMVMPS2eKWM<QVl-3QQI-IPLONOC3.20C-E-1C3.80C3.90C-E-2C-F,CWC4.40C-DC3.100C-E-lC3.110C-E-2C3.120C3.1C-F,CWC4o30C-DPumpsPumpcasingfields.Boltsandstuds.Integrallyweldedsupportattachments.~Componentsupports.Supportsmechanicalandhydraulic.ValvesValvebodyfields.Boltsandstuds.Integrallyweldedsupportattachments.Componentsupports.Supportsmechanicalandhydraulic.VolumetricVolumetricSurfaceVisualVisualVolumetricVolumetricSurfaceVisualVisualH0UI88rt4808Q'LOHQCONVC)Ul5hSI'6IQMUloortHmrtQXlor.rI.Ol"uIHP0rI'0III0v59}}
EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS'ARTS'ND MFTllODSOFEXAMINATION COMPONENTS ANDPARTSTOBEEXAMINEDMETIIODAHERMAWVCOClMCl.+~HO~HO<H0B5.6B-L-1B5.8B-PB7.60BW-2B6.210B-G-1B6.220B-G-1B6.230B-G-1B10.30B-K-1B11.30B-K-2B6.6B-M-1B6.8B-PB7.70BW-2PumpPressureBoundaryPumpcasingwelds.Exemptedcomponents.
Bolts,studs,andnuts.ReactorCoolantPumpFlywheel.
ValvePressureBoundaryBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrally weldedattachments.
Component supports.
Valve-body welds.Fxemptedcomponents.
Bolts,studs,andnuts.Volumetric VisualVisualVolumetric andSurfaceVolumetricVolumetric andSurfaceVisualVolumetric VisualVolumetric Visual(IWA-5000)
VisualOH0Ul80rt4808AcDVlQltd)'d&SMUMAtt'Hco&Aft0t.CdHg0rtM880HPP8Im EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS, PARTS,'ND METIIODSOFEXAMINATION COMPONENTS ANDPARTSTOBF.FXAHINEDMETIIODQMZchg3WWMCM~N.>RWNHANH0B6.60B-G-1B6.70B-G-1B3.1B-BB6.80B-G-1B8.20.B-HB2.10B-PB7.20B-G-2Pressurizer CVBoltsandstuds,inplae.Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.
Fxemptedcomponents.
Bolts,studs,andnuts.IIeatExchangers andSteamGenerators Longitudinal andcircumferential welds,including Tubesheet-to-head orshellweldsonthepri-maryside.Volumetric Volumetric andSurfaceVisualSurfaceVisual(IVA-5000)
VisualVolumetric H0tn8eenOQr.vwM5eoddpC)0)5&6Mt]C)O0tH006'mr.rfOrtaMQ0rtM85809CmB3.2B3.3B-DB-FNozzle-to-head weldsandnozzleinsideradiusedsectionontheprimaryside.Nozzle-to-safe-end welds.Volumetric Volumetric andSurfaceB6.90BW-1Boltsandstuds,inplace.Volumetric FXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONFNTS, PARTS,ANDMETIIODSOFEXAMINATION COMPONENTS ANDPARTSToBF.FXAMINEDMETlIODAHRRchlOWWMclMc:QVHWWHO4H0B6.40BW-1B6.50B-G-1B7.10BW-2B8.10B-llB1.15B-N-1B1.17B-N-3B1.18B-OB1.19B-PReactorVesselLigaments betweenstudholes.ClosureWashers,bushings.
Bolts,studsandnuts.Integrally-welded attachments.
VesselInterior.
Core-support structures.
Controlroddrivehousings.
Exemptedcomponents.
Pressurizer Volumetric VisualVisualSurfaceVisual.VisualVolumetric Visual(IWA-5000)
H0N8080,8ALOHQMPQotnQtuI'6ISMUtDQftH00ftQlMt'ft0I.tZIHg0rtMS8808B2.1B2.2B2.3B2.4B-BB-DB-FLongitudinal andcircumferential welds.Nozzle-to-vessel weldsandnozzle-to-vessel radiusedsection.lleaterpenetrations.
Nozzle-to-safe-end welds.Volumetric Volumetric Visual(IWA-5000)
Volumetric andSurfaceOVlc)COOm EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1QUALITYGROUPACOMPONENTS, PARTS,ANDMETHODSOFEXAHINATION COMPONENTS ANDPARTSTOBEEXAMINEDHETHODAR3,'M&PNME2aAPMClXVONW0Bl.lB1.2B1.3B1.4B1.5B-AB-BB-DB-EReactorVesselLongitudinal andcircumferential shallweldsincoreregion.Longitudinal andcircurmferential weldsinshell{otherthanthoseofCategoryB-AandB-C)andmeridional andcircumferential beamweldsinbottomheadandclosurehead(otherthanthoseofCategoryB-C).Vessel-to-flange andhead-to-flange circumferen-tialwelds.Primarynozzle-to-vessel weldsandnozzleinsidetiagwelds.
Vesselpenetrations, including controlroddriveandinstrumentation penetrations.
Volumetric Volumetric Volumetric Volumetric Visual(IWA-5000)
H0M8ert4Kle0eQl'NmH5WmggMc)mQlh5>'dweMUwAAHco&m'EOt'N0Ito&50rtWe880gClm8Bl.6Nozzle-to-safe-end welds.Volumetric andSurfaceB6.10B-G-1B6.20B-G-1B6.30B-G-1Closureheadnuts.Closurestuds,inplace.Closurestuds,whenremoved.SurfaceVolumetric Volumetric andSurface C1.1C-AC1.2C3.10C4.10C-DC3.20C3.30C-EC-EC2.1C2.2C2.3C-FeC-GC-F,CWC-F,CWC4.20C3.40C3.50C3.60C-DC-E-1C-E-2EXAMINATION CATEGORYITFMTABLENo.IWC-2520TABLF.ISI1.2QUALITYGROUPBCOMPONENTS'ARTS'ND MFTllODSOFEXAHINATION COHPONENTS ANDPARTSTOBEFXAHINEDPressureVesselsCircumferential buttvelds.Nozzle-to-vessle velds.Integrally-welded supportattachments.
Boltsandstuds.-Component supports.
Supportsmechanical andhydraulic.
PipingCircumferential buttvelds.Longitudinal veld)ointsinfittings.
Branchpipe-to-pipe veld)oints.Boltsandstuds.Integrally veldedsupportattachments.
Component supports.
Supportsmechanical andhyraulic.
MF.TllODVolumetric Volumetric SurfaceVolumetric VisualVisualVolumetric Volumetric Volumetric Volumetric SurfaceVisualVisualOARP.M&WWvlc'sClWMcA<HW'H0lA88rt4808Q'EOH5co85'uotnmRI'0MS(OUu)OrtHmrtfuQ'LDt0I.lxlHg0rtMeN80mMm8VlCO EXAMINATION CATEGORYITEMTABLENo.IWC-2520TABLEISI1.2(Cont'd)COMPONENTS, PARTSlANDMETIIODSOFEXAMINATION COMPONFNTS ANDPARTSTOBEFXAMINEDMFTIIODQaplQRMIOMVMPS2eKWM<QVl-3QQI-IPLONOC3.20C-E-1C3.80C3.90C-E-2C-F,CWC4.40C-DC3.100C-E-lC3.110C-E-2C3.120C3.1C-F,CWC4o30C-DPumpsPumpcasingfields.Boltsandstuds.Integrally weldedsupportattachments.
~Component supports.
Supportsmechanical andhydraulic.
ValvesValvebodyfields.Boltsandstuds.Integrally weldedsupportattachments.
Component supports.
Supportsmechanical andhydraulic.
Volumetric Volumetric SurfaceVisualVisualVolumetric Volumetric SurfaceVisualVisualH0UI88rt4808Q'LOHQCONVC)Ul5hSI'6IQMUloortHmrtQXlor.rI.Ol"uIHP0rI'0III0v59}}

Revision as of 13:36, 29 June 2018

to App B of QA Program for Inservice Insp
ML17258A980
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/21/1981
From: ANDERSON C R, CURTIS A E
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17258A979 List:
References
NUDOCS 8104280389
Download: ML17258A980 (35)


Text

QUALITY'ASSURANCE MANUALGINNASTATIONREV.PAGE422AEFFECTIVE DATEE"ROCHESTER GAS&ELECTRIC'CORPORATION ay,81SIGNATURE DATETITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPREPAREDBYQUALITYASSURANCE REVIEWAPPROVEDBY:V/~i/S(ProramTableofContentsIntroduction:

Program:Discussion ISI1.0ScopeandResponsibility ISI,2.0ISI3.0.Inspection Intervals ExtentandFrequency ISI4.0Examination MethodsISI5.0Evaluation ofExamination ResultsISI6.0RepairRequirements IISI7.0SystemPressureTestingISI8.0ISI9.0RecordsandReportsExemptions

References:

Tables:ISI1.1QualityGroupAComponents, PartsandMethodofExamination ISI1.2QualityGroupBComponents, PartsandMethodofExamination Attachment A-Quality,GroupsA,B,and.CExemptions ICIrpI QUALITYASSURANCE MANUALGINNASTATIONTITLE)APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/81222OF4252CINTRODUCTION Appendix'Bof.thisQuali~tyAssurance Manualdescribes Ginna'sInservice Inspection'rogram forthe120monthinspection intervalcommencing January1,1980andendingDecember31,1989.Includedinthisprogramarethefollowing portionsof-systemsand/orcomponents:

QualityGroupAComponents QualityGroupBComponents QualityGroupCComponents HighEnergyPipingOutsideofContainment SteamGenerator TubingReactorCoolantPumpFlywheels Following theguidanceofReference 1,SectionXIoftheCode,Ginna'sInservice Inspection Programadherestothere-quirements ofSection50.55aoftheCodeofFederalRegulations, Reference 2.Thisprogram,however,excludesthecontrolsoftheAuthorized NuclearInspector, Enforcement Authority, Re-portingSystems,'andN-StampISymbol.TheInservice Inspection'rogram forQualityGroupsA,BandCcomponents, asdefinedinRegulatory Guide1.26,Refer-ence3,iscontrolled byGinna'sQualityAssurance ProgramforStationOperation.

Thissameprogramwhichisalsoincompliance withthe,referenced SectionXI,providesthemostacceptable guidelines andlatesttechniques currently beingutilizedintheperformance ofaninservice inspection.

RepairstoQualityGroupsA,BandCcomponents shallbeperformed inaccordance withtheOwner'sDesignSpecification andConstruction Codeofthecomponent orsystem.LatereditionsoftheConstructio'n CodeorASMESectionIII,eitherinitsentiretyorportionsthereof,canalsobeused.Ifrepairweldingcannotbeperformed inaccordance withtheserequirements, thenArticle4000ofReference 11willbeused.Asindicated inRochester GasandElectric's report/Reference 4,andAugmented Inservice Inspection Programforhighenergypipingoutsideofcontainment hasbeenes-tablished.

Theinspection programprovidesforvolumetric examination onallcircumferential buttweldssituatedatdesignbreaklocations oratdiscontinuity locations whereprobablefailurecouldoccur.Surveillance ofthesewelds 0IP QUALITYASSURANCE MANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/813F22candetectmaterialchangesinadvanceofapotential failure,therebyassuringthatthedesignbasisorconsequential mainsteamorfeedwater breakwillnotoccur.TheInservice Inspection Programforsteamgenerator tubeswasdeveloped tomeettheguidanceofReference 5.Atregularintervals, tubeswithineachlegofthesteamgenerator areexaminedandevaluated foracceptable tubewallthickness.

TheInservice Inspection Programforreactorcoolantpumpflywheels wasdeveloped tomeettheguidanceofReference 12.Attheintervals suggested, thereactorcoolantpumpflywheelwillbeexaminedbyeitherthevolumetric orsurfaceexami-nationmethod,andevaluated tothespecified acceptance criteria.

Identification isgiveninSection9.0ofGinna'sInservice Inspection Programforthoseareaswhichdeviatefromtherequirements ofReference 1.Whereapplicable, currently approvededitionandaddendasofSectionXIwillbeutilizedforclarification andguidance.

ItistheintentofRochester GasandElectricCorporation, tocontinually applyappropriate changesintheCodewhichimprovestheoverallqualityofGinna'stotalInservice Inspection Program.PROGRAMISI1.0ScoeandResonsibilit Components ofQualityGroupsAandBarelistedinTablesISI-1.1and1.2,respectively.

QualityGroupCcomponents areidentified inAppendixAofGinna'sQualityAssurance Manual.Thespecificcomponents tobeexaminedforeachQualityGroupshallbedefinedintheExamination Plansbytitleand/ornumber.1.2TheInservice Inspection Programforhighenergypipingoutsideofcontainment consistsofmainsteamandfeedwater pipingweldsisdetailedintheExamination PlanforHighEnergyPiping.

0gllAuII QUALITYASSURANCEMANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/814224252C1.3TheInservice Inspection Programforsteamgenerator tubes,whichisoutlinedinthispro-gram,wasdeveloped totheguidanceprovidedinReference 5,.isIdetailedinGinna'sstationprocedures.

1.4TheInservice Inspection Programforreactorcoolantpumpflywheels, whichisoutlinedinthisprogram,wasdeveloped totheguidancepro-videdinReference 12,isdetailedinGinna'sstationprocedures.

ISI2.0Insec'tionIntervals 2.12.2Theinservice inspection (ISI)intervals forQualityGroupAcomponents shallbetenyearintervals ofservicecommencing January1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalforQualityGroupAcomponents.

Thetenyearexamination planshalldescribethe'istribution ofexaminations withintheinspection intervalinaccordance withIWB-2400ofReference 1~Theinservice inspection intervals forQualityGroupBcomponents shallbetenyearintervals ofservicecommencing onJanuary1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalforQualityGroupBcomponents.

Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withIWC-2400ofReference 1.2.3Theinservice inspection intervals forQualityGroupCcomponents shallbetenyearintervals ofservicecommencing onJanuary1,1970.ThisprogramdefinestheISIrequirements forthesecondintervalQualityGroupCcomponents.

Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withIWD-2400ofReference

1.

rl QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGEOF225/01/812.4Theinservice inspection intervals forthehighenergypipingoutsideofcontainment shallbetenyearintervals ofservicecommencing May1,1973.Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withtherequirements ofReference 4.2.5Theinservice inspection intervals fortheexami-nationofsteamgenerator tubesshallnotbemorethan24months.However,ifoveranominal2yearperiod(e.g.,twonormalfuelcycles)atleast2examinations oftheseparatelegsresultinlessthan10%ofthe.tubeswithdetectable wallpenetration (T20%)andnosignificant (710%)furtherpenetration oftubeswithpreviousindi-cations,theinspection intervaloftheindividual legsmaybeextendedtoonceevery40months.2.6Aspermitted byIWA-2400ofReference 1,theinservice inspection intervalforQualityGroupsA,BandCandhighenergypipingoutsidecon-tainmentmaybeextendedasnecessary.

2.7Theinservice inspection intervals forthereactorcoolantpumpflywheelshallbeapproximately 10yearintervals ofservice.commencing onJanuary1,1970.Forareasofhighstressconcentration attheboreandkeyway,areducedintervalofapproxi-mately3years'shall beapplied.Thetenyearexamination planshalldescribethedistribution ofexaminations withintheinspection intervalinaccordance withtherequirements ofReference 12.ISI3.03.1ExtentandFreuencrQualityGroupAcomponents, aslistedinTableISI-1.1shallbeexaminedtotheextentandfrequency asrequiredinTableIWB-2500ofRefer-ence1.

IJt QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPAGE6OF22DATE5/01/813.2QualityGroupBcomponents, aslistedinTableISI-1.2,shallbeexaminedtotheextentandfrequency asrequiredinTableIWC-2500ofReference 1.3.3QualityGroupCcomponents asdescribed inthetenyearexamination planshallbeexaminedtotheextentandfrequency requiredinIWD-2400andIWD-2600ofReference 1.3.4Highenergypipingweldsoutsideofcontainment shallbeexaminedtothefollowing extentandfrequency:

3.4.1Duringeachperiodofthefirstinspection inter-val,allweldsat.designbreaklocations andone-thirdofallweldsatlocations where'weldfailurewouldresultinunacceptable consequences, willbevolumetrically examined.

3.4.2Duringeachperiodofsucceeding intervals, one-thirdofallweldsatdesignbreaklocations andone-third ofallweldsatlocations whereaweldfailurewouldresultinunacceptable consequences, shallbevolumetrically examined.

3.5Theextentandselection ofsteamgenerator tubeexaminations shallbeasdescribed inSectionsC.4andC.5ofReference 5,withtheinterpretation thatexamination inalegofallpreviously defective tubes(Q20%detectable wall'enetration) anduptoamaximumoftwohundredpreviously defect-free tubes(420%detectable wallpene-tration)isdeemedsufficient inmeetingtherequirements ofReference 5.3.5.1Intheeventaprimarytosecondary leakexceedstechnical specification limit,alimitednumberoftubesshallbeexaminedatthenextrefueling outage.3.5.2Intheeventofaseismicoccurance greaterthanthatforwhichtheplantisdesignedtocontinueoperation, Reference 6,aspecialexamination ofalimitednumberoftubesshallbeconducted.

foIi'HtIP4I QUALITYASSURANCE MANUALGINNASTATIONTITLEiAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/81722OF3.5.3Intheeventofamajorsteamlineorfeedwater linebreak,oraloss-of-coolant accident(LOCA)whichimposesasignificant pressuretransient onthesteamgenerators andrequiresactuation oftheengineered safe-guards, aspecialexami-nationofalimitednumberoftubesshallbeconducted.

3.6Thereactorcoolantpumpflywheel, listedinTableISI-1.1,shallbeexaminedtotheextentandfrequency asrequiredinReference 12.ISI4.0Examination Methods4.1QualityGroupsAandBcomponents shallbeexaminedbytherequiredvisual,surfaceorvolumetric methods.Theseexaminations shallincludeoneoracombination ofthefollowing:

visual,liquidpenetrant, magneticparticle, ultrasonic, eddy-current orradiographic exami-nation.Thesemethods,shallasaminimum,beinaccordance wj.ththerulesofIWA-2000ofReference 1.4.1.14.1.1.1Ultrasonic examinations shallbeperformed inaccordance withthefollowing:

Forferriticvesselswithwallthickness of2-1/2inchesorgreater',

anultrasonic examination shallbeconducted inaccordance withtherulesofAppendixIofReference 1.4.1.1.24.1.1.3Forferriticpipingsystems,anultrasonic exami-nationshallbeconducted inaccordance withtherulesofAppendixIIIofReference 7.Forcomponents otherthanthoselistedin4.1.1.1and4.1.1.2,anultrasonic examination shallbeconducted inaccordance withtherulesofArticle5ofReference 8.4.1.1.4Allindications whichproducearesponsegreaterthan,50%ofthereference levelshallberecorded.

0f~'l QUALITYASSURANCE MANUALGINNASTATIONTITLEtAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/8182242~52C4.1.1.5Allindications whichproducearesponse~100%ofthereference levelshallbeinvestigated totheextentthat,theoperatorcanevaluatetheshape,identity',

andlocationofallsuchre-flectorsintermsoftheacceptance/rejection standards ofIWA-3100(b)ofReference 1.Thelengthofreflectors shallbemeasuredbetweenpointswhichgiveamplitudes equalto100%ofthereference level.4.2QualityGroupCcomponents shallbevisuallyexaminedforleakageduringasystempressuretest.4.3Highenergypipingweldsoutsideofcontainment shallberadiographically examined.

4.4Steamgenerator tubesshallbeexaminedbyavolumetric method(e.g.eddycurrent)oral-ternative methodwhichisacceptable.

4.5,ReactorcoolantIpumpflywheelsshallbeexaminedbytherequired;surface andvolumetric methods,inaccordance withtherequirements ofIWA-2200ofReference 1.ISI5.0Evaluation ofExamination Results5.1Theevaluation ofnondestructive examination resultsshallbeinaccordance withArticleIWB-3000ofReference 1.Allreportable indications shallbesubjecttocomparison withpreviousdatatoaidinitscharacterization andindeter-miningitsorigin.5.25.2.1QualityGroupBComponents Theevaluation ofnondestructive examination re-sultsshallbeinaccordance withArticleIWC-3000ofReference 1.Allreportable indications shallbesubjecttocomparison withpreviousdatatoaidinitscharacterization andindetermining itsorigin.5.3QualityGroupCComponents c~Aj"IJ QUALITYASSURANCE MANUALGINNA"STATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE5/01/8122OF4252C5.3.1Theevaluation ofthevisualexamination resultsshallbeinaccordance withArticleIWA-5000ofReference 1.5.4HighEnergyPiping5.4.1Theevaluation ofnondestructive examination resultsshallbeinaccordance withReference 9.5.5Indications thatwererecordedinpreviouspre-serviceorinservice inspections andwhichwerenotcharacterized aspropagating flawsareacceptable forcontinued service.5.6Theevaluation ofanycorrodedareashallbeperformed inaccordance withArticleIWA-5000ofReference 11.5.7SteamGenerator TubesandTubeSleeveCombinations 5.7.1Theevaluation ofnondestructive examination resultsshallbeasfollows:5.7.1.1Plantoperation mayresumewhenalltubesandsleevesarewithinacceptable wallthickness criteriaandtheconditions of(a)or(b)aremet:(a)Whenlessthan10percentofpreviously defect-free tubesorsleevesexamined, (i.e.C20%ofwallpenetration) havedeveloped detectable wallpenetrations ofgreaterthan20%,or(b)Whenpreviously degradedtubesorsleevesexhibitfurtherwallpenetration ofC10%.NOTE:Anacceptable tubewallthickness isonewhichcansustainaLOCAincombination withaseismicoccurrence, forwhichtheplantisdesignedtocontinueoperation, withoutalossoffunctiontoClass1systems,Reference 8.Sleevesmaybeusedtoprovideanacceptable tube.

J(flN0/I.J1V QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE10OF4C225.7.1.25.7.1.35.7.1.4Ifnomorethan3tubesorsleeveshaveunacceptable wallthickness andthecriteriaof5.7.1.1areotherwise met,plantoperation mayresumeaftercorrective measureshavebeentaken.Whentheabovecriteriaarenotmet,thesituation shallbeimmediately reportedtotheNuclearRegulatory Commission.

Plantoperation mayresumeaftercorrective measuresaretaken.All'bnormal degradation ofsteamgenerator tubesshallbereportedwithaLicenseeEvent,Report(LER)inaccordance withTechnical Specification require-,ments.Steamgenerator tubesthathavedefectindications P40%throughwall,asindicated byeddycurrent,shallberepairedbypluggingorbysleeving."

Steamgenerator sleevesthathavedefectindi-cations+30%throughwall,asindicated byeddycurrent,shallberepairedbyplugging.

ISI6.0ReairReuirements 6.1RepairofQualityGroupsA,BandCcomponents shallbeperformed inaccordance withtheappli-cableSubsections ofReference 11.6.26.2.1Examinations associated withrepairsormodifi-cationsshallmeettheapplicable designandinspection Coderequirements asdescribed inthefollowing paragraphs:

WheneverQualityGroupsA,BorCSystemmodifi-cationsorrepairshavebeenmadewhichinvolvenewstrengthweldsoncomponents greaterthan2inchesdiameter, thenewweldsshallreceivebothsurfaceand100percentvolumetric nondestructive examinations.

6.2.2Wheneversystemmodifications orrepairshavebeenmadewhichinvolvenewstrengthweldsonQualityGroupsA,BorCcomponents of2inchesorless,asurfaceexamination shallbeperformed.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE11OF22426RC6.3SurfacedefectsinQualityGroupsA,BorCbolts,studs,nutsandligaments mayberemovedbymechanical meansprovidedtheremovalofthatdefectdoesnotalterthebasicconfiguration oftheitem.Bolts,studsandnutsthathavede-fectsthatcannotberemovedbymechanical meansshallbereplaced.

6.4Repairofhighenergypipingweldsoutsideofcontainment shallbeperformed inaccordance withtheapplicable Codespecified inReference 11.6.5RepairofSteamGenerator Tubes6.5.1Repairofsteamgenerator tubesthathaveunaccept-,

abledefectsshallbeperformed byusingatubepluggingtechnique orbysleeving.

Ifsleevingistobeperformed therequirements of6.5.3mustbeimplemented.

6.5.2Preventative sleevingoftubesaspartofapre-ventative maintenance

.programmayalsobeaccom-plishedprovidedtherequirements of6.5.3aremet.6.5.3Duringeachsteamgenerator inspection amaximumof25sleevesmaybeinstalled ineachsteamgenerator forrepairorpreventative maintenance.

Anyadditional sleeveinstallation shallrequiretheapprovaloftheNuclearRegulatory Commisssion, NuclearReactorRegulation Branch.6.6,Repairofsteamgenerator sleevesthathaveunacceptable defectsshallbeperformed byusingatubepluggingtechnique.

6.7ISI7-0Repairofreactorcoolantpumpflywheelthathaveunacceptable defectsshallbeperformed inaccordance withReference 12.SstemPressureTestin7.1GeneralRequirements 7.1.1Systempressuretestshallbeconducted inaccordance withArticleIWA-5000ofReference

11.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATE5/01/81PAGE12OF42~52C227.1.2Repairsofcorrodedareasshallbeperformed inaccordance withSection6.0ofthisprogram.7.2QualityGroupAComponents 7.2.1Wheneverthereactorcoolantsystemisclosedafterithasbeenopened,thesystemshallbeleaktestedtotherequirements ofArticleIWB-5000ofReference 11.Temperature andpressurerequirements ofFigure3.1-1,Section3.1ofGinna's"Technical Specifications" shallnotbeexceeded.

7.2.2Atorneartheendofeachinspection

interval, ahydrostatic pressuretestshallbeperformed onthereactorcoolantsystemcomponents.

Thistestshallbeconducted inaccordance withtherequire-mentsofArticleIWB-5000ofReference 11.Testpressures andtemperatures shallbemaintained foratleastfourhourspriortoperforming thevisualexamination.

Section3.1ofGinna's"Technical Specification" shallnotbeexceeded.

7.3QualityGroupBComponents 7.3.1Atorneartheendofeachinspect'ion

interval, ahydrostatic pressuretestshallbeperformed onQualityGroupBSystemsandComponents.

Thistestshallbeconducted inaccordance withtherequirements ofArticleIWC-5000ofReference 11.WhenQualityGroupAsystemsandcomponents arealsobeingpressurized, thepressureandtemper-atureshallcomplywiththerequirements ofParagraph 7.2.2ofthisAppendix.

Thistesttemperature andpressureshallbemaintained foratleast10minutespriortotheperformance ofthevisualexamination.

7.4QualityGroupCComponents 7.4.1QualityGroupCcomponents shallhavesystempressuretestinaccordance withArticleIWD-5000ofReference

11.

5<~,t1F, QUALITYASSURANCE

'ANUALGINNASTATIONTITLEeAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalPAGE5/01/81OF4252C22ISI8.0RecordsandReorts8.1Recordsandreportsdeveloped fromthoseexami-nationsperformed inaccordance withthisAppendixshallbemaintained inaccordance withArticleIWA-6000ofReference 11.ISI9-0Exemtions9.1QualityGroupsA,BandCcomponents exemptions areidentified inAttachment AtothisAppendix.

However,Paragraphs IWB-1220andIWC-1220ofReference 1exemptcertaincomponents fromexami-nations,wherecertainconditions aremet.Theseexemptions willbeappliedtothecomponents listedonTablesISI-1.1and1.2withtheresultthat.onlythosenon-exempt components arelistedherein.REFERENCES 1.AmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCode(B&PVC)SectionXI"RulesforInservice Inspection ofNuclearPowerPlantComponents",

1974EditionthroughSummer1975Addenda.2.CodeofFederalRegulations, Title10,Part50,datedJanuary1,1978.3.NuclearRegulatory Commission, Regulatory Guide1.26,Revision1,datedFebruary1976"Quality-Group Classifi-cationsandStandards forWater,Steam,andRadioactive Waste-Containing Components ofNuclearPowerPlants".4.Rochester GasandElectricCorporation Report"EffectsofPostulated PipeBreaksOutsidetheContainment Building",

datedOctober29,1973.5.NuclearRegulatory Commission, Regulatory Guide1.83,Revision1,datedJuly1975,"Inservice Inspection ofPressurized WaterReactorSteamGenerator Tubes".6.Ginna'sFinalSafetyAnalysisReport,Section2.9.3.7.ASME,BGPVC,SectionXI,1974EditionthroughSummer1976Addenda.

'Kl~JAl~eII(

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBGinnaStationInservice Inspection ProgramForthe1980-1989 IntervalDATEPAGE42~52C5/01/811422OF8.ASME,BGPVC,SectionV,1974EditionthroughSummer1975Addenda.9.USASB31.1.0-1967,"PowerPiping".10.ASME,BGPVC,SectionIII,1974EditionthroughSummer1975Addenda.11.ASME,B6PVCSectionXI,1977EditionthroughSummer1978Addenda.12.NuclearRegulatory Commission, Regulatory Guide1.14,Revision1,datedAugust.1975,"ReactorCoolantPumpFlywheelIntegrity".

~g~rik3),~P"'")fIpg~pypi'lJ,J EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1~1(Cont'd)COHPONFNTS, PARTS,ANDMETHODSOFEXAHINATION COMPONENTS ANDPARTSTOBF.EXAHINFDMETHODQHRRZMx3WVM<<M<<RWQHPtON086.1008-G-186.110BW-188.30,8-H88.4083.98-P84.18-F87.30,BW-287.40HeatExchangers andSteamGenerators Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.

Exemptedcomponents.

Bolts,studs,andnuts.PipingPressureBoundarySafe-endtopipingweldsandsafe-endinbranchpipingwelds.Volumetric andSurfaceVisualSurfaceVisual(IWA-5000)

VisualVolumetric andSurfaceHQM86rt4er.e0OAr<<08c)V)5h3I'0we<<oU'ClQ<<tHm<<tQQOr%Hg0<<t'u8880Rjll986.150B-G-186.160B-G-186.170BW-I84.58-JBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Circumferential andlongitudinal pipewelds.Volumetric Volumetric andSurfaceVisualVolumetric OOmVlCOI EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)CONPONENTS, PARTS,ANDMETIIODSOFEXAMINATION COlfPONENTS ANDPARTSTOBEFXAHINFDMFTHODQMRRZMIOWQMKUlCRWWHOQHId0PipingPressureBoundaryB4.6B-JB4.7B-JB4.8B10.10B-K-1B11.10B-K-2B4.11B-PB7~50BW-2Branchpipeconnection weldssixinchdiameterandsmaller.SurfaceSocketwelds.Integrally weldedattachments.

Component supports.

Exemptedcomponents.

Bolts,studsand-nuts.SurfaceSurface.VisualVisual(IWA-5000)

VisualPumpPressureBoundaryBranchpipeconnection weldsexceeding sixinchVolumetric diameter.

HQIll8Illrt4III0IIIArvMIMEco55C)OlIllI'08MUClOCtMCortIllR'LoIQI.tdH5Qrt068QMIll9B6.180B-G-1B6.190B-G-1B6.200B-G-1B10.20B-K-1B11.20B-K-2Boltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.

Component supports.

Volumetric Volumetric andSurfaceVisualSurfaceVisualVlCDCO5IN0

~~~

EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS'ARTS'ND MFTllODSOFEXAMINATION COMPONENTS ANDPARTSTOBEEXAMINEDMETIIODAHERMAWVCOClMCl.+~HO~HO<H0B5.6B-L-1B5.8B-PB7.60BW-2B6.210B-G-1B6.220B-G-1B6.230B-G-1B10.30B-K-1B11.30B-K-2B6.6B-M-1B6.8B-PB7.70BW-2PumpPressureBoundaryPumpcasingwelds.Exemptedcomponents.

Bolts,studs,andnuts.ReactorCoolantPumpFlywheel.

ValvePressureBoundaryBoltsandstuds,inplace.Boltsandstuds,whenremoved.Bolting.Integrally weldedattachments.

Component supports.

Valve-body welds.Fxemptedcomponents.

Bolts,studs,andnuts.Volumetric VisualVisualVolumetric andSurfaceVolumetricVolumetric andSurfaceVisualVolumetric VisualVolumetric Visual(IWA-5000)

VisualOH0Ul80rt4808AcDVlQltd)'d&SMUMAtt'Hco&Aft0t.CdHg0rtM880HPP8Im EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONENTS, PARTS,'ND METIIODSOFEXAMINATION COMPONENTS ANDPARTSTOBF.FXAHINEDMETIIODQMZchg3WWMCM~N.>RWNHANH0B6.60B-G-1B6.70B-G-1B3.1B-BB6.80B-G-1B8.20.B-HB2.10B-PB7.20B-G-2Pressurizer CVBoltsandstuds,inplae.Boltsandstuds,whenremoved.Bolting.Integrally-welded attachments.

Fxemptedcomponents.

Bolts,studs,andnuts.IIeatExchangers andSteamGenerators Longitudinal andcircumferential welds,including Tubesheet-to-head orshellweldsonthepri-maryside.Volumetric Volumetric andSurfaceVisualSurfaceVisual(IVA-5000)

VisualVolumetric H0tn8eenOQr.vwM5eoddpC)0)5&6Mt]C)O0tH006'mr.rfOrtaMQ0rtM85809CmB3.2B3.3B-DB-FNozzle-to-head weldsandnozzleinsideradiusedsectionontheprimaryside.Nozzle-to-safe-end welds.Volumetric Volumetric andSurfaceB6.90BW-1Boltsandstuds,inplace.Volumetric FXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1(Cont'd)COMPONFNTS, PARTS,ANDMETIIODSOFEXAMINATION COMPONENTS ANDPARTSToBF.FXAMINEDMETlIODAHRRchlOWWMclMc:QVHWWHO4H0B6.40BW-1B6.50B-G-1B7.10BW-2B8.10B-llB1.15B-N-1B1.17B-N-3B1.18B-OB1.19B-PReactorVesselLigaments betweenstudholes.ClosureWashers,bushings.

Bolts,studsandnuts.Integrally-welded attachments.

VesselInterior.

Core-support structures.

Controlroddrivehousings.

Exemptedcomponents.

Pressurizer Volumetric VisualVisualSurfaceVisual.VisualVolumetric Visual(IWA-5000)

H0N8080,8ALOHQMPQotnQtuI'6ISMUtDQftH00ftQlMt'ft0I.tZIHg0rtMS8808B2.1B2.2B2.3B2.4B-BB-DB-FLongitudinal andcircumferential welds.Nozzle-to-vessel weldsandnozzle-to-vessel radiusedsection.lleaterpenetrations.

Nozzle-to-safe-end welds.Volumetric Volumetric Visual(IWA-5000)

Volumetric andSurfaceOVlc)COOm EXAMINATION CATEGORYITEMTABLENo.IWB-2500TABLEISI1.1QUALITYGROUPACOMPONENTS, PARTS,ANDMETHODSOFEXAHINATION COMPONENTS ANDPARTSTOBEEXAMINEDHETHODAR3,'M&PNME2aAPMClXVONW0Bl.lB1.2B1.3B1.4B1.5B-AB-BB-DB-EReactorVesselLongitudinal andcircumferential shallweldsincoreregion.Longitudinal andcircurmferential weldsinshell{otherthanthoseofCategoryB-AandB-C)andmeridional andcircumferential beamweldsinbottomheadandclosurehead(otherthanthoseofCategoryB-C).Vessel-to-flange andhead-to-flange circumferen-tialwelds.Primarynozzle-to-vessel weldsandnozzleinsidetiagwelds.

Vesselpenetrations, including controlroddriveandinstrumentation penetrations.

Volumetric Volumetric Volumetric Volumetric Visual(IWA-5000)

H0M8ert4Kle0eQl'NmH5WmggMc)mQlh5>'dweMUwAAHco&m'EOt'N0Ito&50rtWe880gClm8Bl.6Nozzle-to-safe-end welds.Volumetric andSurfaceB6.10B-G-1B6.20B-G-1B6.30B-G-1Closureheadnuts.Closurestuds,inplace.Closurestuds,whenremoved.SurfaceVolumetric Volumetric andSurface C1.1C-AC1.2C3.10C4.10C-DC3.20C3.30C-EC-EC2.1C2.2C2.3C-FeC-GC-F,CWC-F,CWC4.20C3.40C3.50C3.60C-DC-E-1C-E-2EXAMINATION CATEGORYITFMTABLENo.IWC-2520TABLF.ISI1.2QUALITYGROUPBCOMPONENTS'ARTS'ND MFTllODSOFEXAHINATION COHPONENTS ANDPARTSTOBEFXAHINEDPressureVesselsCircumferential buttvelds.Nozzle-to-vessle velds.Integrally-welded supportattachments.

Boltsandstuds.-Component supports.

Supportsmechanical andhydraulic.

PipingCircumferential buttvelds.Longitudinal veld)ointsinfittings.

Branchpipe-to-pipe veld)oints.Boltsandstuds.Integrally veldedsupportattachments.

Component supports.

Supportsmechanical andhyraulic.

MF.TllODVolumetric Volumetric SurfaceVolumetric VisualVisualVolumetric Volumetric Volumetric Volumetric SurfaceVisualVisualOARP.M&WWvlc'sClWMcA<HW'H0lA88rt4808Q'EOH5co85'uotnmRI'0MS(OUu)OrtHmrtfuQ'LDt0I.lxlHg0rtMeN80mMm8VlCO EXAMINATION CATEGORYITEMTABLENo.IWC-2520TABLEISI1.2(Cont'd)COMPONENTS, PARTSlANDMETIIODSOFEXAMINATION COMPONFNTS ANDPARTSTOBEFXAMINEDMFTIIODQaplQRMIOMVMPS2eKWM<QVl-3QQI-IPLONOC3.20C-E-1C3.80C3.90C-E-2C-F,CWC4.40C-DC3.100C-E-lC3.110C-E-2C3.120C3.1C-F,CWC4o30C-DPumpsPumpcasingfields.Boltsandstuds.Integrally weldedsupportattachments.

~Component supports.

Supportsmechanical andhydraulic.

ValvesValvebodyfields.Boltsandstuds.Integrally weldedsupportattachments.

Component supports.

Supportsmechanical andhydraulic.

Volumetric Volumetric SurfaceVisualVisualVolumetric Volumetric SurfaceVisualVisualH0UI88rt4808Q'LOHQCONVC)Ul5hSI'6IQMUloortHmrtQXlor.rI.Ol"uIHP0rI'0III0v59